2013.09 - 2018.06, 开云网页登录 , 核科学与技术, 博士
2009.09 - 2013.06, 开云网页登录 , 核工程与核技术, 学士

2022.12 - 至今，开云网页登录 ，副教授
2021.06 - 2022.12，保罗谢勒研究所(PSI) - 瑞士，PSI学者/玛丽·居里学者
2020.09 - 2021.06，保罗谢勒研究所(PSI) - 瑞士，博士后
2019.01 - 2019.12，密歇根大学 - 美国，博士后
2018.06 - 2020.06，开云网页登录 ，博士后

反应堆结构材料的环境失效行为评价与服役寿命预测，包括：
1. 商用反应堆结构材料(不锈钢、镍基合金等)的腐蚀失效行为与机理研究
2. 先进反应堆候选结构材料(ATF包壳、增材制造不锈钢等)的腐蚀失效行为评价与预测
3. 反应堆水化学及其缓蚀机制研究
4. 多尺度材料表征技术

 国家自然科学基金青年项目: 梯度晶粒结构优化高铬奥氏体不锈钢高温耐蚀机制研究, 2025.01-2027.12, 负责人
 中核集团青年英才项目: Cr涂层包壳在一回路复杂水化学环境下的溶解模型研究, 2024.07-2027.06, 负责人
 PSI学者/玛丽·居里学者基金(EU-MSCA): Fundamental understanding of zinc-injection to mitigate stress corrosion cracking under light water reactor coolant conditions, 2021.06-2023.06, 负责人
 中国博士后科学基金面上项目(一等)：压力对310S不锈钢在超临界水中的应力腐蚀开裂行为研究, 2018.11-2020.03, 负责人
 瑞士核安监局(ENSI)基金: Zinc injection in nuclear power plants to mitigate environmentally-assisted cracking of structural materials, 2020.09-2024.03, 主要研究人员
 国家重点研发计划: 超临界水冷堆核能系统材料与化学研发, 2019.11-2022.10, 研究骨干
 美国电力研究所(EPRI)项目: OLNC Pt deposition characterization and correlation with ECP, 2021.07-2021.12, 主要完成人
 美国电力研究所(EPRI)和美国西屋电气(Westinghouse Electric)联合项目: IASCC Testing of Irradiated Stainless Steels for KOH Qualification, 2019.01-2019.12, 主要完成人
 国家自然科学基金面上项目: 晶间碳化物对冷变形690合金应力腐蚀开裂的影响机理研究, 2019.01-2022.12, 研究骨干
 国家重点研发计划: 应力-腐蚀-热时效耦合环境核电关键材料服役行为高通量评价技术, 2017.09-2021.08, 研究骨干
 国家重点基础研究发展计划(973计划): 海洋动力装备构件腐蚀疲劳形成机理与组织精确调控, 2014.07-2018.10, 参与

第一作者论文：
[1] Kai Chen, Adrianna Mackiewicz, Hans-Peter Seifert, Sannakaisa Virtanen, Stefan Ritter, Role of Zn injection on mitigating stress corrosion cracking initiation of Alloy 182 weld metal in simulated light water reactor environment, Corrosion Science 221 (2023) 111364.
[2] Kai Chen, Adrianna Mackiewicz, Sannakaisa Virtanen, Pascal V. Grundler, Hans-Peter Seifert, Stefan Ritter, Effect of zinc injection on mitigating stress corrosion cracking initiation of structural materials in light water reactor primary water, Corrosion Reviews 41 (3) (2023) 387-398.
[3] Kai Chen, Lefu Zhang, Zhao Shen*, Understanding the surface oxide evolution of T91 ferritic-martensitic steel in supercritical water through advanced characterization, Acta Materialia 194 (2020) 156-167.
[4] Kai Chen, Jiamei Wang, Lefu Zhang, Hui Wang, Xuguang An, Yifeng Li, Jianqiang Zhang, Zhao Shen*, Xiaoqin Zeng*, A high-resolution study of the different surface state effects on the corrosion behaviors of a ferritic steel and an austenitic steel in supercritical water, Corrosion Science 209 (2022) 110757.
[5] Kai Chen, Lefu Zhang, Zhao Shen*, Xiaoqin Zeng*, Revealing the oxidation mechanism of 310S stainless steel in supercritical water via high-resolution characterization, Corrosion Science 200 (2022) 110212.
[6] Kai Chen, Zhu Liu, Xianglong Guo, Hui Wang, Zhao Shen*, Xiaoqin Zeng*, Effect of surface finishing on the oxidation characteristics of a Fe-21Cr-32Ni alloy in supercritical carbon dioxide, Corrosion Science 195 (2022) 110019.
[7] Kai Chen, Lefu Zhang, Shengchuan Wu, Zhao Shen*, High-resolution characterization of the internal and external oxidation of austenitic alloys in supercritical water, Scripta Materialia 197 (2021) 113814.
[8] Kai Chen, Zhao Shen*, A study on the surface and crack tip oxidation of Alloy 600 through high-resolution characterization, Corrosion Science 169 (2020) 108616.
[9] Kai Chen*, Jiamei Wang, Zhao Shen, Donghai Du, Xianglong Guo, Lefu Zhang*, Peter L. Andresen, Effect of intergranular carbides on the cracking behavior of cold worked Alloy 690 in subcritical and supercritical water, Corrosion Science 164 (2019) 108313.
[10] Kai Chen, Jiamei Wang, Donghai Du*, Xianglong Guo, Lefu Zhang*, Characterizing the effects of in-situ sensitization on stress corrosion cracking of austenitic steels in supercritical water, Scripta Materialia 158 (2019) 66-70.
[11] Kai Chen, Michael R. Ickes*, Michael A. Burke, Gary S. Was, The effect of potassium hydroxide primary water chemistry on the IASCC behavior of 304 stainless steel, Journal of Nuclear Materials 558 (2022) 153323.
[12] Kai Chen, Jiamei Wang, Zhao Shen, Donghai Du, Xianglong Guo, Bin Gong, Jinhua Liu, Lefu Zhang*, Comparison of the stress corrosion cracking growth behavior of cold worked Alloy 690 in subcritical and supercritical water, Journal of Nuclear Materials 520 (2019) 235-244.
[13] Kai Chen, Jiamei Wang, Donghai Du, Peter L. Andresen, Lefu Zhang*, dK/da effects on the SCC growth rates of nickel base alloys in high-temperature water, Journal of Nuclear Materials 503 (2018) 13-21.
[14] Kai Chen, Donghai Du, Wenhua Gao, Xianglong Guo, Lefu Zhang*, Peter L. Andresen, Effect of cold work on the stress corrosion cracking behavior of Alloy 690 in supercritical water environment, Journal of Nuclear Materials 498 (2018) 117-128.
[15] Kai Chen, Jiamei Wang, Haozhan Su, Lefu Zhang*, Investigation on the stress corrosion crack initiation and propagation behavior of Alloy 600 in high temperature water, Corrosion 74 (2018) 1395-1405.
[16] Kai Chen, Jiamei Wang, Donghai Du*, Xianglong Guo*, Lefu Zhang, Peter L. Andresen, Stress corrosion crack growth behavior of 310S stainless steel in supercritical water, Corrosion 74 (2018) 776-787.
[17] Kai Chen, Donghai Du, Lefu Zhang*, Peter L. Andresen, Corrosion fatigue crack growth behavior of Alloy 690 in high temperature pressurized water, Corrosion 73 (2017) 724-733.
[18] 陈凯, 杜东海, 陆辉, 张乐福*, 石秀强, 徐雪莲. TiN夹杂物对690合金传热管疲劳裂纹扩展行为的影响, 稀有金属材料与工程 47 (2018) 1180-1184.
[19] 陈凯, 杜东海, 陆辉, 张乐福*. 690 合金腐蚀疲劳裂纹扩展研究, 稀有金属材料与工程 46 (2017) 2130-2136.
[20] 陈凯, 杜东海,张乐福*. 690合金在压水堆环境中的腐蚀疲劳裂纹扩展行为, 开云网页登录 学报 51 (2017) 1281-1286.
[21] 陈凯, 杜东海, 张乐福*, 徐雪莲, 石秀强, 孟凡江, 鲍一晨, 刘晓强.. 基于直流电压降法的传热管疲劳裂纹扩展速率测量, 工程科学学报 10 (2015) 1331-1337.
[22] 陈凯, 杜东海, 陆辉, 张乐福*, 石秀强, 徐雪莲. 690合金传热管疲劳裂纹扩展研究, 开云网页登录 学报 48 (2014) 1639-1643.
[23] 陈凯, 杜东海, 陆辉, 张乐福*. 304L不锈钢在高温高压水中的腐蚀疲劳裂纹扩展行为, 腐蚀与防护 39 (2018) 17-23.
[24] 陈凯, 杜东海, 陆辉, 张乐福*. 核电汽轮机转子腐蚀疲劳裂纹的扩展行为, 腐蚀与防护 37 (2016) 887-891.
[25] 陈凯, 杜东海, 陆辉, 张乐福*, 徐雪莲, 石秀强, 孟凡江, 鲍一晨, 刘晓强. 用直流电压降法研究316LN不锈钢的疲劳裂纹扩展行为, 机械工程材料 40 (2016) 7-10.
通讯作者论文：
[1] Jiamei Wang, Tianyu Zhu, Yichen Bao, Xiaoqiang Liu, Xiuqiang Shi, Xianglong Guo, Zhongli Han, Peter L. Andresen, Lefu Zhang*, Kai Chen*, Insights into the stress corrosion cracking propagation behavior of Alloy 690 and 316 L stainless steel in KOH versus LiOH oxygenated water, Corrosion Science 224 (2023) 111556.
[2] Haozhan Su, Tao Huang, Jiamei Wang, Lefu Zhang*, Kai Chen*, The cracking growth behavior of a sensitized Alloy 800H in supercritical water, Journal of Nuclear Materials 583 (2023) 154509.
[3] Haozhan Su, Dayun Sun, Yufan Jiang, Yunzhi Shi, Lefu Zhang*, Kai Chen*, Peter L. Andresen, Investigation on the corrosion behavior of Alloy 800H at various levels of deformation, Corrosion Science 212 (2023) 110926.
[4] Jiamei Wang, Yule Wu, Tianyu Zhu, Kai Chen*, Jinna Mei, Fei Xue, Haitao Sun*, Wujiang Ma, Yuanhua Wang, Peter L Andresen, Lefu Zhang, Effect of thermal aging on the environmental assisted cracking behavior of 308L weld metal in high temperature water, Corrosion Science 211 (2023) 110902.
[5] Jiamei Wang, Tianyu Zhu, Kai Chen*, Yichen Bao, Wujiang Ma, Miaomiao Zhang, Xianglong Guo*, Peter L Andresen, Lefu Zhang, Investigations on the SCC initiation behavior of cold worked 316 L in high temperature oxygenated water at constant loads, Corrosion Science 203 (2022) 110336.
[6] Jiamei Wang, Haozhan Su, Kai Chen*, Donghai Du, Lefu Zhang, Zhao Shen, Effect of δ-ferrite on the stress corrosion cracking behavior of 321 stainless steel, Corrosion Science 158 (2019) 108079.
[7] Donghai Du, Jiamei Wang, Kai Chen*, Lefu Zhang*, Peter L. Andresen, Environmentally assisted cracking of forged 316LN stainless steel and its weld in high temperature water, Corrosion Science 147 (2019) 69-80.
[8] Jiamei Wang*, Tianyu Zhu, Yaolei Han, Jinna Mei, Fei Xue, Kai Chen*, Donghai Du, Peter L Andresen, Lefu Zhang, Miaomiao Zhang, Environment assisted cracking of 308L weld metal in high temperature water, Journal of Nuclear Materials 557 (2021) 153275.
[9] Jiamei Wang, Tianyu Zhu, Kai Chen*, Donghai Du, Peter L. Andresen, Lefu Zhang*, Effect of dissolved oxygen and hydrogen on the stress corrosion cracking behavior of alloy 600 in high temperature water, Journal of Nuclear Materials 543 (2021) 152603.
[10] Jiamei Wang, Haozhan Su, Kai Chen*, Donghai Du*, Lefu Zhang*, Yongduo Sun, Corrosion fatigue crack growth behavior of alloy 52 M in high-temperature water, Journal of Nuclear Materials 528 (2020) 151848.
[11] Jiamei Wang, Haozhan Su, Farzin Ajmand, Lefu Zhang*, Kai Chen*, Effects of corrosion potential, dissolved oxygen, and chloride on the stress corrosion cracking susceptibility of a 316NG stainless steel weld joint, Corrosion 75 (2019) 946-959.
合作作者论文：
[1] Zhao Shen, Kai Chen, Hongbing Yu, Benjamin Jenkins, Yanru Ren, Naganand Saravanan, Guanze He, Xiaonan Luo, Paul Bagot, Michael P. Moody, Lefu Zhang, Sergio Lozano-Perez, New insights into the oxidation mechanisms of a ferritic-martensitic steel in high-temperature steam, Acta Materialia 194 (2020) 522-539.
[2] Donghai Du, Kai Chen, Lefu Zhang, Zhao Shen*, Microstructural investigation of the nodular corrosion of 304NG stainless steel in supercritical water, Corrosion Science 170 (2020) 108652.
[3] Zhao Shen*, Kai Chen, David Tweddle, Guanze He, Koji Arioka, Sergio Lozano-Perez, Characterization of the crack initiation and propagation in Alloy 600 with a cold-worked surface, Corrosion Science 152 (2019) 82-92.
[4] Xianglong Guo*, Kai Chen, Wenhua Gao, Zhao Shen, Lefu Zhang*, Corrosion behavior of alumina-forming and oxide dispersion strengthened austenitic 316 stainless steel in supercritical water, Corrosion Science 138 (2018) 297-306.
[5] Xianglong Guo, Kai Chen, Wenhua Gao, Zhao Shen, Ping Lai, Lefu Zhang*, A research on the corrosion and stress corrosion cracking susceptibility of 316L stainless steel exposed to supercritical water, Corrosion Science 127 (2017) 157-167.
[6] Lefu Zhang, Kai Chen, Jiamei Wang, Xianglong Guo, Donghai Du*, Peter L. Andresen, Effects of Zinc injection on stress corrosion cracking of cold worked austenitic stainless steel in high-temperature water environments, Scripta Materialia 140 (2017) 50-54.
[7] Wenhua Gao, Kai Chen, Xianglong Guo*, Lefu Zhang, Fracture toughness of type 316LN stainless steel welded joints, Materials Science and Engineering A 685 (2017) 107-114.
[8] Donghai Du, Kai Chen, Hui Lu, Lefu Zhang*, Xiuqiang Shi, Xuelian Xu, Peter L. Andresen, Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water, Corrosion Science 110 (2016) 134-142.
[9] Yang Ding, Yuting Lv, Kai Chen, Bingjie Zhao, Yuanfei Han, Liqiang Wang, Weijie Lu*, Effects of microstructure on the stress corrosion cracking behavior of nickel-aluminum bronze alloy in 3.5% NaCl solution, Materials Science & Engineering A 733 (2018) 361-373.
[10] Zhao Shen, Kai Chen, Xianglong Guo, Lefu Zhang*, A study on the corrosion and stress corrosion cracking susceptibility of 310-ODS steel in supercritical water, Journal of Nuclear Materials 514 (2019) 56-65.
[11] Lefu Zhang, Kai Chen, Donghai Du, Wenhua Gao, Peter L. Andresen, Xianglong Guo*, Characterizing the effect of creep on stress corrosion cracking of cold worked alloy 690 in supercritical water environment, Journal of Nuclear Materials 492 (2017) 724-733.
[12] Donghai Du, Kai Chen, Lun Yu, Hui Lu, Lefu Zhang*, Xiuqiang Shi, Xuelian Xu, SCC crack growth rate of cold worked 316L stainless steel in PWR environment, Journal of Nuclear Materials 456 (2015) 228-234.
[13] Donghai Du, Miao Song, Kai Chen, Lefu Zhang, Peter L. Andresen, Effect of deformation level and orientation on SCC of 316L stainless steel in simulated light water environments, Journal of Nuclear Materials 531 (2020) 152038.
[14] Donghai Du*, Jiamei Wang, Kai Chen, Lefu Zhang*, Stress corrosion cracking behavior of warm forged 316L stainless steel at different orientations, Journal of Nuclear Materials 522 (2019) 220-225.

核材料科学，研究生

[1] 陈凯, 汪家梅, 苏豪展, 杜东海, 张乐福, 一种薄壁管试样加载装置, 中国, CN201811165199 (授权)
[2] 陈凯, 张乐福, 苏豪展, 汪家梅, 沈朝, 一种腐蚀介质下金属材料腐蚀速率在线测量装置及方法, 申请号：2023112279058 (授权)
[3] 陈凯, 张乐福, 苏豪展, 汪家梅, 沈朝, 一种高温高压水环境下氧化膜破裂应变原位测量系统, 申请号：2023105185732
[4] 张乐福, 陈凯, 汪家梅, 沈朝, 内嵌式密封高温高压反应釜装置, 申请号：2023111092468

2022年欧洲腐蚀大会 (EUROCORR 2022) 核材料腐蚀分会场主席
2021年欧洲腐蚀大会 (EUROCORR 2021) 核材料腐蚀分会场主席
美国核协会 (American Nuclear Society) 会员
欧洲腐蚀协会 (EFC) 会员
期刊审稿(> 40篇): Corrosion Science • Journal of Nuclear Materials • Corrosion • Metallurgical and Materials Transactions A • Materials Science and Engineering: A • Materials & Design • International Journal of Mechanical Sciences • Construction & Building Materials • Advances in Mechanical Engineering • The Journal of Supercritical Fluids • Journal of Materials Science & Technology • Applied Surface Science • International Journal of Pressure Vessels and Piping • Engineering Failure Analysis • Materials Characterization • Chinese Journal of Aeronautics •Corrosion Engineering Science and Technology

 中核集团青年英才-菁英人才（2024年）
 中国国际大学生创新大赛全国金奖—指导教师（2023年）
 上海市“海外高层次人才计划”（2023年）
 PSI学者/玛丽·居里学者（2021年）
 上海市博士后日常经费资助（2018年）